Letter Sequence Approval |
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TAC:MB0695, Ventilation System Envelope Allowed Outage Time (Approved, Closed) TAC:MB0696, Ventilation System Envelope Allowed Outage Time (Approved, Closed) |
|
MONTHYEARML0135504172002-01-0808 January 2002
Request for Additional Information, Application for Conversion to Improved Technical Specifications, Section 3.7
Project stage: RAI
ML0215400082002-06-0303 June 2002
Draft Safety Evaluation Conversion to Improved Technical Specifications
Project stage: Draft Approval
ML0215403012002-06-0303 June 2002
Draft of Safety Evaluation
Project stage: Draft Approval
ML0218300892002-07-15015 July 2002
Environmental Assessment and Finding No Significant Impact for the Proposed Conversion to the Improved TSs
Project stage: Other
ML0222100432002-07-26026 July 2002
Technical Specifications for License Amendment Nos. 158 and 149, Pages 1.1-1 to 3.4.13-1 (174 Pages)
Project stage: Acceptance Review
ML0220706582002-07-26026 July 2002
Individual Notice of Issuance, License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications
Project stage: Other
ML0221403592002-07-26026 July 2002
Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B2.1.1-1 to B3.3.1-66 200 Pages)
Project stage: Acceptance Review
ML0221403702002-07-26026 July 2002
Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B.3.3.2-1 to B3.4.13-13 (185 Pages)
Project stage: Acceptance Review
ML0221403942002-07-26026 July 2002
Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B3.4.14-1 to B3.7.7-7 (186 Pages)
Project stage: Other
ML0221404122002-07-26026 July 2002
Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B3.7.8-1 to B3.9.6-4 (194 Pages)
Project stage: Acceptance Review
ML0222100542002-07-26026 July 2002
Technical Specifications for License Amendment Nos. 158 and 149, Pages 3.4.13-1 to 5.0-4.5 (215 Pages)
Project stage: Acceptance Review
ML0230400542002-07-26026 July 2002
Attachment 2 to Safety Evaluation of Amendment No. 149 - Table a - Administrative Controls
Project stage: Approval
ML0230401182002-07-26026 July 2002
Attachment 4 to Safety Evaluation of Amendment No. 149 - Table L - Less Restrictive Changes
Project stage: Approval
ML0230401212002-07-26026 July 2002
Attachment 3 to Safety Evaluation of Amendment No. 149 - Table M - More Restrictive Changes
Project stage: Approval
ML0230401282002-07-26026 July 2002
Attachment 5 to Safety Evaluation of Amendment of 149 - Table Lr - Less Restrictive - Relocated Details
Project stage: Approval
ML0230401442002-07-26026 July 2002
Attachment 6 to Safety Evaluation of Amendment No. 149 - Table R - Relocated Specifications
Project stage: Approval
ML0230401512002-07-26026 July 2002
Attachment 7 to Safety Evaluation of Amendment No. 149 - Table U - Unused Numbers
Project stage: Approval
ML0220706542002-07-26026 July 2002
License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications (Safety Evaluation)
Project stage: Approval
ML0220706132002-07-26026 July 2002
License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications (Cover Letter, Amendment, License Pages)
Project stage: Other
2002-06-03
[Table View] |
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Category:Safety Evaluation
MONTHYEARML23356A0032024-01-17017 January 2024
Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
ML23215A1672023-12-15015 December 2023
Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3
ML23115A4072023-04-26026 April 2023
Correction of License Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B
ML22357A1002023-03-31031 March 2023
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility
ML22300A2232022-11-0101 November 2022
Issuance of Amendments 241 and 229 TSTF-577 Revised Frequencies for Steam Generator Tube Inspections
ML22270A3252022-09-30030 September 2022
(Prairie Island), Unit 2 - Authorization and Safety Evaluation for Alternative Request No. RR-08
ML22181A0002022-08-17017 August 2022
Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels
ML22166A3892022-07-28028 July 2022
Issuance of Amendments 239 and 227 24-Month Operating Cycle
ML22061A2062022-04-0101 April 2022
Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0
ML21312A0212021-11-23023 November 2021
Issuance of Amendment Nos. 237 and 225 Inoperable Cooling Water System Supply Header
ML21008A0012021-03-19019 March 2021
Issuance of Amendment Nos. 236 and 224 Low Temperature Overpressure Protection
ML20346A0202021-03-15015 March 2021
Issuance of Amendment Nos. 235 and 223, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML20356A0022021-02-0505 February 2021
Issuance of Amendment Nos. 234 and 222, Revise Technical Specifications 3.2.1 and 5.6.5 Identified in Westinghouse Nuclear Safety Advisory Letters NSAL-09-05, Revision 1, and NSAL-15-1
ML20283A3422020-11-18018 November 2020
Issuance of Amendment Nos. 233 and 221 Adoption of Technical Specifications Task Force Traveler TSTF-547, Clarification of Rod Position Requirements
ML20217L1852020-10-0202 October 2020
Issuance of Amendment Nos. 232 and 220 Increase the Integrated Leak Rate Test Program Type a and Type C Test Frequency
ML20276A0032020-10-0202 October 2020
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20210M0142020-09-0808 September 2020
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules
ML20230A0512020-09-0303 September 2020
Reactor Vessel Material Surveillance Capsule Withdrawal Schedules
ML20153A4012020-06-0101 June 2020
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code
ML20135G9922020-05-29029 May 2020
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code
ML20134H9582020-05-29029 May 2020
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code
ML19276F6842019-11-12012 November 2019
Issuance of Amendments 230 and 218 Issuance of Amendments Adoption of 10 CFR 50.69 - Risk Informed Caterization and Treatment of Structure, Systems and Components of Nuclear Power Reactors
ML19232A1512019-11-0707 November 2019
Issuance of Amendments Modifying the Design Basis for Quality Classification of Certain Fuel Handling Equipment
ML19140A4472019-07-30030 July 2019
Issuance of Amendments Revision to National Fire Protection Association (NFPA) Standard NFPA 805 Modifications
ML19177A3802019-07-0303 July 2019
Reactor Vessel Material Surveillance Capsule Withdrawal Schedules
ML19128A1332019-06-0606 June 2019
Issuance of Amendments TSTF-439 Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO
ML19045A4802019-04-16016 April 2019
Issuance of Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B
ML19046A1662019-02-25025 February 2019
Relief from the Requirements of the ASME Code
ML19029A0942019-01-29029 January 2019
Issuance of Amendment No. 213, One-Time Technical Specification Change to Extend Completion Time for EDGs D5 and D6 (Emergency Circumstances)
ML18270A0152018-10-19019 October 2018
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code
ML18100A7882018-05-0101 May 2018
Issuance of Amendment Special Heavy Lifting Device Nondestructive Examination Frequency (CAC Nos. MG0072 and MG0073; EPID L-2017-LLA-0280)
ML17346A3612018-03-0606 March 2018
Issuance of Amendment Nos. 224 and 211 to Adopt Changes to the Emergency Plan
ML17362A2022018-03-0505 March 2018
Issuance of Amendment Concerning Revision to the Prairie Island Nuclear Generating Plant, Units 1 and 2 Emergency Plan (CAC Nos. MF9345 and MF9346; EPID L-2017-LLA-0175)
ML17334A1782017-11-30030 November 2017
Issuance of Amendment Request Related to Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122, EPID L-2015-LLA-0002) Non-Proprietary
ML17310B2392017-11-28028 November 2017
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195)
ML17163A0272017-08-0808 August 2017
Issuance of Amendments Transition to NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants
ML17130A7162017-06-20020 June 2017
Issuance of Amendments Technical Specification 3.8.7 Inverters-Operating
ML17110A2752017-05-0404 May 2017
Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML16320A0212016-11-28028 November 2016
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Review of Changes to the Northern States Power Company Quality Assurance Topical Report
ML16256A5142016-10-13013 October 2016
Issuance of Amendment One-Time Extension for Technical Specification Surveillance Requirement 3.8.4.3. DC Sources - Operating
ML16246A2002016-10-0404 October 2016
Request for Relief 1RR-4-11 and 2-RR-4-11 Associated with Certain Inservice Inspection of Component Welds for the Fourth 10-Year Interval
ML16133A4062016-06-16016 June 2016
Issuance of Amendment Nos. 217 and 205, Adoption of Technical Specifications Task Force TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation (CAC Nos. MF6449 and MF6450)
ML15264A2092015-11-30030 November 2015
Issuance of Amendment Nos. 216 and 204 Regarding Revisions to Technical Specification 3.3.3 and Renewed Facility Operating License
ML15229A1762015-08-26026 August 2015
Issuance of Amendment Nos. 215 and 203 Regarding Revision to Licensing Basis Analysis for a Waste Gas Decay Tank Rupture
ML15196A2132015-08-17017 August 2015
Requests 1-RR-4-9 and 2-RR-4-9 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program
ML15196A2412015-08-12012 August 2015
Requests 1-RR-5-6 and 2-RR-5-6 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program
ML15196A2272015-08-12012 August 2015
Requests 1-RR-5-3 and 2-RR-5-3 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program
ML15196A2212015-08-12012 August 2015
Requests 1-RR-5-1 and 2-RR-5-1 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program
ML15196A4322015-08-0606 August 2015
Requests 1-RR-4-11 and 2-RR-4-11 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program
ML15196A1952015-08-0606 August 2015
Request 2-RR-4-10 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program
2024-01-17
[Table view] |
Text
Table R- Relocated Specifications ITS '-'ection 1.0 - Use and Application (D( ' Io. are numbered sequentially by ITS Section)
DOC No. Summary " I Ca t-et ShangeeControl I .
INONE INONE ----- NON_. ONEiNUNj.N 1
Prairie Island ITS July 2002
Table R - Relocated Specifications ITS Section 2.0 - Safety Limits (DOC No. are numbered sequentially by ITS Section) 1 Prairie Island ITS I I ^ffr
Table R - Relocated Specifications ITS Section 3.0 - LCO Applicability/SR Applicability (DOC No. are numbered sequentially by ITS Section)
Location Change Conoll.*6seat II DOC No. II Summary Proces I-, '..
I SI] 1. . . . .. n1-%,k-i I.NUNt
,,-,7I jINU3NE.
m.n mp:I iNONE INONE 1
Prairie Island ITS July 2002
Table R - Relocated Specifications ITS Section 3.1 - Reactivity Control Systems (DOC No. are numbered sequentially by ITS Section)
PCntrol CT5Sect O
1NONE Location Change DOC No. Summary INONE /NONE -INONE "INONE" I
Prairie Island ITS July 2002
Table R - Relocated Specifications ITS Section 3.2 - Power Distribution Limits (DOC No. are numbered sequentially by ITS Section) r-
.dcatlon 7Change Control Process ,o CTS Sect SDOC No.I Summary I I"rI-Ia I IlIVI II10CFR50.59 LCO 3.11 .A I
i i ______ ll Relocates CTS Specification for Core Surveillance Instrumentation. This IT01KA IHM iR3.2-49 II specification has been relocated because it does not meet the NRC Policy Statement TS Selection Criteria for inclusion in the TS.
I Prairie Island ITS
Table R - Relocated Specifications ITS Section 3.3 - Instrumentation (DOC No. are numbered sequentially by ITS Section)
DOC NChange ONo. 1 Summary ILocItion TM I Procdss 1 Undt-1rU.rn Control *,. CTS Sect LI.11AJ3 Q r-j R3.3-03 iTRM 1 II'CbU5.59 JL1UU 2.3.L;,
Relocates CTS Specification for Control Rod Stops.
- I m I I 1I Table 4.1 -1C USAR 10CFR50.59 R3.3-1 15 R elocated various instruments in accordance with an approved LAR. Functions 13, 16, 17, 19, 20 and 31.
TRM OCFR5O.59 I10CFR50.59 Table 3.5-1 R3.3-1 52 Relocated specific Functions for high temperature vent ducts. Function 8 and Table 4.1-1C Function 24 1
Prairie Island ITS July 2002
Table R - Relocated Specifications ITS Section 3.4 - Reactor Coolant System (DOC No. are numbered sequentially by ITS Section)
Location Changb Control I CTS Sect DOC Summary No... . :1CFR0.5i9 I....-........ 1, _.
_LGU 3.1 .A.3 an dl ITIRM II R3.4-56 Relocated CTS reactor vessel head vent system LCO, Required Actions, and SR 4.18 I iviv II yuwl I .
associated Surveillances.
PTLR, Approved NRC LCO 3.1.B.2 R3.4-66 Relocated CTS pressurizer heatup and cool down Specification including LCO, TRM methodology Required Actions, and Surveillances. and 100CFR 50.59.
Approved NRC LCO 3.1 .B.3 TR R3.4-67 Relocated CTS steam generator pressure/temperature limits specification. LR, methodology and 10 CFR 50.59 1
Prairie Island ITS July 2002
Table R - Relocated Specifications ITS Section 3.5 - Emergency Core Cooling Systems (DOC No. are numbered sequentially by ITS Section)
Location ChagE CTS Sect NContl DOC No. Summary .Proceiss " ý,:,ý NONE NONE INONE_ INONE .. ,NONE---
1 Prairie Island ITS
Table R - Relocated Specifications ITS Section 3.6 - Containment Systems (DOC No. are numbered sequentially by ITS Section)
Location Char!
Summary 1P1 Prniri* l.lnd ITS
Table R - Relocated Specifications ITS Section 3.7 - Plant Systems (DOG No. are numbered sequentially by ITS Section)
Locaton ,Change Control CTS Sect Summary
,Process TRM 10CFR50.59 LCO 3.4.C Relocated CTS Steam Exclusion System LCO and SR requirements. and SR 4.8.G Relocated CTS requirement to limit the number of recently discharged fuel TRM 10CFR50.59 LCO 3.8.C assemblies stored in the small pool (Pool 1).
"Re o-fc;a-tej-dCTS snubber LCO and SR requirements. CFR50.59 IRM LCO 3.12, R3.7-79 SR 4.13-1 stop valves, FTRM 10CFR50.59 Table 4.1-2A R3.7-81 Relocated CTS requirements for periodic testing of the turbine intercept valves.
governor valves and prior TRM 0CFR50.59 R 4.19 Relocated Specification requirements to inspect AB crane lifting devices 1 to handling heavy loads.
Prairie Island ITS
Table R - Relocated Specifications ITS Section 3.8 - Electrical Power Systems (DOC No. are numbered sequentially by ITS Section) j" hange od-: cntrol, 6 TS6Sect Set D No.j Summary [LbbAtifio Pro iess ,-'. -
NONE ýNONE INONE ýNUNIE NONE I ______________________
I Prairie Island ITS
.iiIiv Pnn907/16/2002
Table R- Relocated Specifications ITS Section 3.9 - Refueling Operations (DOC No. are numbered sequentially by ITS Section)
DOC No. II Summary I Location ! Control Proc.a.: C Sect' INONE NONE INONE NONE NONE 1
Prairie Island ITS July 2002
Table R - Relocated Specifications ITS Section 4.0 - Design Features ITS Section)
(DOC No. are numbered sequentially by I
Prairie Island ITS July 2002
Table R - Relocated specifications ITS Section 5.0 - Administrative Controls (DOC No. are numbered sequentially by ITS Section) 1 Prairie Island ITS I. .1. ^ ""f'n
